ML20034G662
| ML20034G662 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-12-A-110) |
| Issue date: | 03/05/1993 |
| From: | Jeffrey Mitchell Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034G663 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9303100347 | |
| Download: ML20034G662 (9) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION w
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WASHING TON. D. C. 20555
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET N0. 50-395 c
VIRGIL C. SUMMER NUCLEAR STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated September 23, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable aso;; once (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissic t's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No.
NPF-12 is hereby amended to read as follows:
9303100347 930305 PDR ADOCK 05000395 P
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i (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.110
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
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h-l Jocelyn A. Mitchell, Acting Director l
Project Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation t
Attachment:
Changes to the Technical Specifications Date of Issuance:
Marr.n 5, 1993 f
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ATTACHMENT TO LICENSE AMENDMENT N0,110 l
l TO FACILITY 0PERATING LICENSE NO. NPF-12 l
t DOCKET NO. 50-395
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i Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are indicated by marginal lines.
Remove Paoes Insert Paoes I
l-2 1-2 3/4 6-1 3/4 6-1 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 3/4 6-19 3/4 6-19 i
3/4 6-20 i
3/4 6-20a t
3/4 6-20b l
3/4 6-20c
. i B 3/4 6-5 B 3/4 6-5 f
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DEFINITIONS CONTAINMENT IK _5RITY i
1.7 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
o 1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.4, b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and The sealing mechanism associated with each penetration (e.g.,
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welds, bellows, or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document that provides core operating limits for the current operating reload cycle.
The cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.11.
Plant operation within these operating limits is addressed in individual specifications.
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
~he thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
SUMMER - UNIT 1 1-2 Amendment No. ES, 110
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i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT i
CONTAINMENT INTEGRITY l
LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APDLICABILITY: MODES 1, 2, 3 and 4.
ACTION-Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I SURVEILLANCE REOUIREMENTS i
i 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are i
closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for-valves that are open under administrative control as permitted by Specification 3.6.4.
i b.
By verifying that each containment air lock is in compliance with the requirements of Specification.3.6.1.3.
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After each closing of each penetration subject to Type B testing, i
except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at Pa (47.1 psig) and j
verifying that when the measured leakage rate for these seals is-l added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all-other Type B and C penetrations, the combined i
leakage rate is less than 0.60 La.
- Except valves, blind flanges, and deactivated automatic vah es which'are located inside the containment'and are locked, sealed or otherwise secured i
in the closed position. These penetrations shall be verified closed during i
each COLD SHUTDOWN except that such verification need not be performed more i
often than once per 92 days.
SUMMER - UNIT 1 3/4 6-1 Amendment No.110 l
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f CONTAINMENT SYSTEMS f
3/4.6.4 CONTAINMENT ISOLATION VALVES I
LIMITING CONDITION FOR OPERATION 3.6.4 Each containment isolation valve shall be OPERABLE.*
l APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and j
either:
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a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
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b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least l
one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD i
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I The provisions of Specification 3.0.4 do not apply.
l SURVEILLANCE REOUIREMENTS 1
4.6.4.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or i
replacement work is performed on the valve or its associated actuator, control, or power circuit by performance of a cycling test and verification of isolation time.
.-t 4.6.4.2 Each containment. isolation valve shall be demonstrated OPERABLE l
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during the COLD SHUTOOWN or REFUELING MODE AT LEAST ONCE PER 18 MONTHS BY:
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i a.
Verifying that on a Phase A containment isolation test signal, each -
Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase.B-isolation valve actuates to its isolation position.
c.
Verifying that on a Reactor Building Purge and Exhaust isolation test signal, each Purge and Exhaust valve actuates to its isolation j
position.
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- Locked or sealed closed valves may be opened on an intermittent basis under administrative control.
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SUMMER - UNIT 1 3/4 6-17 Amendment No. 110 i
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CONTAff ENT SYSTEMS SURVEILLANCE REOUIREMENTS (continued) 4.6.4.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
a.
SUMMEft - UNIT 1 3/4 6-Id Amendment No. 110
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I TABLE 3.6-1 l
3 CONTAINMENT ISOLATION VALVES Y A i
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Pages 3/4 6-19, 3/4 6-20, 3/? 6-20a, 3/4 6-20b.and 3/4 6-29c deleted i
1 Suf94ER - UNIT 1 3/4 6-19 Amendment No. 110 l
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2 CONTAINMENT SYSTEMS BASES 3/4.6.4 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the
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reactor building atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the reactor building atmos-phere or pressurization of the reactor building and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits required by the safety analysis
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for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consisten: with the assumotions used in the analyses for a LOCA.
The openir.7 of locked or sealed clos?d containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing an operator, who is in constant communication with control room, at the valve controls. (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves.
3/4.6.5 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within the reactor building below its flammable limit during post-LOCA conditions. Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7,
" Control of Combustible Gas Concentrations in Containment following a LOCA,"
March 1971.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.
SUMMER - UNIT 1 B J/4 6-5
.\\mendment No. 110